v. 9 n. 2B (Suppl.) (2021)

XXI Meeting on Nuclear Reactor Physics and Thermal Hydraulics (XXI ENFIR) and VI ENIN 2019

• A Method for the evaluation of knowledge management systems

  Claudio Henrique dos Santos Grecco, Silas Cordeiro Augusto, Jaqueline Tavares Viana de Souza, Paulo Victor Rodrigues Carvalho, Adriana Loureiro Davila

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• Experimental evaluation of natural convection in the IPR-R1 Triga research reactor at 264 kW and 105 kW

  Amir Zacarias Mesquita

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• Neutronic Evaluation of MSBR System Using MCNP Code

  Clarysson Alberto Mello da Silva, Alana Lima Vieira, Isabella Resende Magalhães, Claubia Pereira

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• Modified methodology for determining the temperature profiles of inverted u-tubes steam generators used in pwr power plants

  Marcos Filardy Curi, José Luiz Zanon Zotin, Luiz Carlos Chaves

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• Small break loss of coolant accident of 200 cm² in cold leg of primary loop of Angra2 nuclear power reactor evaluation

  EDUARDO MADEIRA BORGES, GAIANÊ SABUNDJIAN

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• One-step coupled calculations (Serpent-OpenFOAM) for a fuel rod of the IPR-R1 triga reactor

  Tiago Augusto Santiago Vieira, Rebeca Cabral Gonçalves, Izabella Cristina de Paiva Machado, Guilherme Augusto Moura Vidal, Higor Fabiano Pereira Castro, Nataly Lamounier Ribeiro, Marcos Pais Barroso Filho, Wilker Gustavo Ferreira Santos, Daniel de Almeida Magalhães Campolina, Graiciany de Paula barros, Vitor Vasconcelos Araújo Silva, André Augusto Campagnole dos Santos

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• Quality assurance program for Angra 1 licence renewal and long-term operation

  YOUSSEF MORGHI, Amir Zacarias Mesquita, Ana Rosa BALIZA MAIA

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• Thermal hydraulic analysis of a PWR loaded with annular fuel rods

  Wallen Ferreira De Souza, Maria Auxiliadora Fortini Veloso, Antonella Lombardi Costa, Clubia Pereira

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• DEVELOPED LIQUID FILMS FALLING AROUND TAYLOR BUBBLES INSIDE VERTICAL STAGNANT COLUMNS

  Marcos Bertrand de Azevedo

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• Thermal-hydraulics validation of CFD code for light water nuclear reactors against benchmark experimental results

  Deiglys Borges Monteiro, Duvan Alejandro Castellanos Gonzalez, José Rubens Maiorino

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• Scientific knowledge management about Monte Carlo method: a bibliometric analysis on IRD Postgraduate Program in Radiation Protection and Dosimetry

  FELIPE DO CARMO AMORIM, PEDRO PACHECO DE QUEIROZ FILHO, Fernando Barcellos Razuck

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• Simulation of transients in ads reactors in three-dimensional geometry

  José Rafael Nicolao Carneiro, Zelmo Rodrigues de Lima, Alessandro da Cruz Gonçalves

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• Computational simulation of a single Taylor bubble rising in a vertical column with stagnant liquid

  Francisco Rogerio Teixeira Nascimento

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• Entering new markets: nuclear industry challenges

  Luciano Ondir Freire, Delvonei Alves de Andrade

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• Potential advantages of molten salt reactor for merchant ship propulsion

  Luiz Gonzaga de Freitas Neto, Luciano Ondir Freire, Adimir dos Santos, Delvonei Alves de Andrade

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• Effect of compaction pressure on the thermal conductivity of UO2-BeO-Gd2O3 pellets

  Denise das Mercês Camarano, Ana Maria Matildes Dos Santos, Fábio Abud Mansur

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• Knowledge base about risk and safety of nuclear facilities to support analysts and decision-makers

  Antonio Souza Vieira Neto, Amaury Muñoz Oliva, Patrícia da Silva Pagetti de Oliveira, Marcos Costa Hunold, Maria Eugênia Lago Jacques Sauer, Vinicius Andrea

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• Core parametric study for enhancing the radioisotope production in the IEA-R1 research reactor

  Giovanni Laranjo Stefani, Frederico Antônio Genezini, Thiago Augusto Santos, João Manoel de Losada Moreira

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• Reliability and redundancy allocation analysis applied to a nuclear protection system

  Alexander Lucas Busse, João Manoel Losada Moreira

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• Overview of the seismic probabilistic safety assessment applied to a nuclear installation located in a low seismicity zone

  Ellison Amaro de Oliveira, Patricia da Silva Pagetti de Oliveira, Miguel Mattar Neto, Marcos Coelho Maturana

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